SiC/SiC Cladding Materials Properties Handbook
- Brookhaven National Lab. (BNL), Upton, NY (United States)
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
When a new class of material is considered for a nuclear core structure, the in-pile performance is usually assessed based on multi-physics modeling in coordination with experiments. This report aims to provide data for the mechanical and physical properties and environmental resistance of silicon carbide (SiC) fiber–reinforced SiC matrix (SiC/SiC) composites for use in modeling for their application as accidenttolerant fuel cladding for light water reactors (LWRs). The properties are specific for tube geometry, although many properties can be predicted from planar specimen data. This report presents various properties, including mechanical properties, thermal properties, chemical stability under normal and offnormal operation conditions, hermeticity, and irradiation resistance. Table S.1 summarizes those properties mainly for nuclear-grade SiC/SiC composites fabricated via chemical vapor infiltration (CVI). While most of the important properties are available, this work found that data for the in-pile hydrothermal corrosion resistance of SiC materials and for thermal properties of tube materials are lacking for evaluation of SiC-based cladding for LWR applications.
- Research Organization:
- Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
- Sponsoring Organization:
- USDOE
- DOE Contract Number:
- AC05-00OR22725
- OSTI ID:
- 1399957
- Report Number(s):
- ORNL/TM-2017/385
- Country of Publication:
- United States
- Language:
- English
Similar Records
Reinforced Radiation Resistant SiC-SiC Composites for Nuclear Reactors and Fuel Cladding
Assessment of Pre-Irradiation SiC CMC Joint Performance in Representative Cladding Geometries